ML20009G140

Forwards LER 81-033/03L-0.Supersedes 810710 Ltr

ML20009G140
Person / Time
Site:	Browns Ferry
Issue date:	07/23/1981
From:	Green H TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8108030367
Download: ML20009G140 (1)

Text

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,Q r Mr. James P. O'Reilly, Director jg 6[R,3([x g J 'g\

U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement JUL P 11981

• r I Region II q uis. g ll 7 " I2 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 f/

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Dear Mr. O'Reilly:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 1 - DOCKET No. 50-259 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE REPORT BFRO-50-259/81033 This letter supe: ca. des my letter to you on the above subject dated July 10, 1981.

The enclosed report provides details concerning the total "as found" primary containment leak rate which exceeded the allowable leak rate.

This report is submitted in accordance with Browns Ferry unit 1 Technical Specification 6.7.2.b(4).

Very truly yours, TENNESSEE VALLEY AUTHOPlTY J. Green .

irector of Nuclear Power Enclosure (3) J cc (Enclosure):

Director (3) l Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Director (40)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

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Mr. Bill Lavallee Nuclear Safety Analysis Center hs Palo Alto, California 94303 Mr. R. F. Sullivan, NRC Inspector, Browns Ferry 8108030367 810723 PDR ADOCK 05000259 S PDR ..,._;... -

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o e.n t. l dot.it ET '2VMOL H f Vf f,I IJF Sf'filP1l(IPJ Afj() PDQtsAOLE CONSEQUENCES h tank vnea I l,;pj j During refueling operation, the total "as found" primary containment I

g g [ exceeded T.S.4.7.A.2g allowable leak rate of 60 percent of La of 655.9 SCFH.

I 5997.5373 SCFH. There una g, g l Total primary containment "as found" leak rate was I

There were no redundant svstama.

[,g ;j jno danger to the health or safety of the public.

I BFRO-50-259/80022, 79003: 260/78009. 79014_ 80049?

g, g g revious P similar events:

l l;,[ q [296/79017.

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Leakage was caused by deterioration of valve seating surfaces durina nnerneinn-lT l .. l [

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[ y [ _ Prior to returning to power, valves will be repaired and reeacead n7eb satisfactory leakage rates are obtained. Investination of better machada en I gg [

I control leakage continues, such as different valve seatine materinla_ aenrina

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[g g pressitres, and closing times. A0 OISCOVERY DESCRIP, TION

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f.4 Slfi'l'I.F. MENT Al. IN FORM ATION 4.7.A.2.g

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iti st': 50- 259_ / ,81033 T. . hnical Specific.. tion Involve:d 6.7.2.b (4) h c due NRC. 7/14/81 10 o u ted (!nder Tv . hnica' SP eification 1000 Unit 1 Ila!" isf Occurrenet. 6/14/81 Time of Occurrence Identific.iitjon_ and Dese,ription of Occurrence:

The total "as found" primary containment leak rate exceeded the. 60 percent of I.a allowable leak rate of 655.9 SOFH. Refer to attachment 2 which details primary paths and leakage rates.

Conilitions Prior to Occurrence:

Unit 1 - In refueling outage.

Unit 2 - At 71%.

Unit 'l - At 98%.

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Action specified in the Technical Spec 7(ication Surveillance Requirements met

..qe in inoperable entiipment. Describe.

None

.ippar ul Cause if f b os rettec - - -

percrioration of valve seating surfaces during operation.

t d ild,iy '. ih Of ,0ctorrenic.. .

There was no danger to the hea'.th or safety of the public, no release of activity, no damage to the plant or equipment, and no resulting significant chain of events.

(: ort;ective, Action:

Valves will be repaired and retested until satisfactory leakage rates are obtained. Investigation of better methods to control leakage continues, such as different valve seating materials, seating pressures, and -

closing times.

F:ulure D:sf a:

BFRO-50-259/80027., 79003: 260/78009, 79014, 80049; 296/79017 RcDgt, ion : Perff,(,1 - I.if.: lime; llesponsibility - Document Control Supervisor

• ltrvinion : .~m/?y 7.- .

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LER BFRO-50-259/81033 _

Attachment 2 Path Valve (Path Leak Rate (SCFH)

X-7A 1-14/15 333.8026 X-7B 1-26/27 18.0526 X-7c 1-37/38 43.6265 X-7D 1-51/52 481.2574 X-8 1-55/56 5.5055 X-22 32-336/2163 3.8089 X-42 63-525/526 4.1790 X-25 64-17/18/19/76-24 239.1828 P Y-231 64-29/30/32/33/8419 3591.6890 X-37C 68-508 0.2445 X-212 71-14/580 40.5000 X-214 73-23/603 97.2000 3 X-19 77-15A/15B 543.2539 12.4481 I X-205 84-8C/1603 X-50 90-257A/257B 433.0948 a

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